Study on the phase separation behavior of (U,Nd)3O8 powder by high temperature oxidation

  • Fang-Li FanEmail author
  • Cun-Min Tan
  • Jie-Ru Wang
  • Wei Tian
  • Zhi QinEmail author


Several samples of (U1−xNdx)3O8 with different Nd content were prepared by different process. After high temperature oxidation, the final oxidized products were found to be a mixture of small particles Nd-rich (U1−yNdy)O2+v phases and large particles Nd-poor (U1−zNdz)3O8−w phases by XRD and SEM analysis. This study indicated that (U1−xNdx)3O8 powder formed a solid solution firstly at 1100 °C or high. The recrystallization of this solid solution happened and the RE-rich fluorite phase formed concurrently when the temperature began to decrease. The present work will provide more information to understand the oxidation behavior of rare-earth doped U3O8 phase at high temperature.


Spent nuclear fuel High temperature oxidation Lanthanides Phase separation 



This research is supported by the Strategic Priority Research Program of Chinese Academy of Sciences (Nos. XDA21010202, XDA03010402), Young Scholar of CAS “Light of West China” Program for Fang-li Fan (No. 2016-84) and the Natural Sciences Foundation of Gansu Province (No. 17JR5RA298).

Compliance with ethical standards

Conflicts of interest

All authors have no conflicts of interest to declare.


  1. 1.
    Yamaji K (1998) Nuclear power in the global energy-environmental system. Prog Nucl Energy 32:235–241CrossRefGoogle Scholar
  2. 2.
    Toth FL (2014) Nuclear energy and sustainable development. Energy Policy 74:S1–S4CrossRefGoogle Scholar
  3. 3.
    Xiao CL, Fard ZH, Sarma D, Song TB, Xu C, Kanatzidis MG (2017) Highly efficient separation of trivalent minor actinides by a layered metal sulfide (KInSn2S6) from acidic radioactive waste. J Am Chem Soc 139:16494–16497CrossRefGoogle Scholar
  4. 4.
    Guzmán JR, Espinosa-Paredes G, François JL, Martín-del-Campo C, Nuñez-Carrera A (2010) Radiotoxicity of transuranics recycling in heterogeneous fuel assemblies for boiling water reactors. Prog Nucl Energy 52:698–706CrossRefGoogle Scholar
  5. 5.
    Acar BB, Zabunoğlu HO (2013) Comparison of the once-through and closed nuclear fuel cycles with regard to waste disposal area required in a geological repository. Ann Nucl Energy 60:172–180CrossRefGoogle Scholar
  6. 6.
    Yu Shadrin A, Ivanov VB, Skupov MV, Troyanov VM, Zherebtsov AA (2016) Comparison of closed nuclear fuel cycle technologies. Atom Energy 121:119–126CrossRefGoogle Scholar
  7. 7.
    Andrianova EA, Davidenko VD, Tsibulskiy VF (2015) On feasibility of a closed nuclear power fuel cycle with minimum radioactivity. Atom Nucl 78:1259–1263CrossRefGoogle Scholar
  8. 8.
    Chirag KV, Pranav MJ, Avesh KT, Vijay KM (2013) Recovery and purification of Sr(II) in perchloric acid medium. J Radioanal Nucl Chem 295:1737–1742CrossRefGoogle Scholar
  9. 9.
    Salvatores M (2005) Nuclear fuel cycle strategies including partitioning and transmutation. Nucl Eng Des 235:805–816CrossRefGoogle Scholar
  10. 10.
    Salvatores M, Palmiotti G (2011) Radioactive waste partitioning and transmutation within advanced fuel cycles: achievements and challenges. Prog Part Nucl Phys 66:144–166CrossRefGoogle Scholar
  11. 11.
    Ewing RC (2015) Long-term storage of spent nuclear fuel. Nat Mater 14:252–257CrossRefGoogle Scholar
  12. 12.
    Kleykamp H (1985) Chemical states of the fission products in oxide fuels. J Nucl Mater 131:221–246CrossRefGoogle Scholar
  13. 13.
    Yang MS, Choi HB, Jeong CJ, Song KC, Lee JW, Park GI, Kim HD, Ko WI, Kim KH, Lee HH, Park JH (2006) The status and prospect of DUPIC fuel technology. Nucl Eng Technol 38:259–264Google Scholar
  14. 14.
    Yang JH, Yoon JY, Lee JH, Cho YZ (2017) A kaolinite-based filter to capture gaseous cesium compounds in off-gas released during the pyroprocessing head-end process. Ann Nucl Energy 103:29–35CrossRefGoogle Scholar
  15. 15.
    Lee H, Park GI, Kang KH, Hur JM, Kim JG, Ahn DH, Cho YZ, Kim EH (2011) Pyroprocessing technology development at KAERI. Nucl Eng Technol 43:317–328CrossRefGoogle Scholar
  16. 16.
    Lee JS, Song KC, Yang MS, Chun KS, Rhee BW, Hong JS, Park HS, Rim CS, Keil H (1993) Research and development program of KAERI for DUPIC (Direct Use of Spent PWR Fuel in CANDU Reactors). In: Proceedings of international conference and technology exhibition on future nuclear system, GLOBAL’93, Seattle, USA, 12–17 September, pp 733–739Google Scholar
  17. 17.
    Lee JW, Park GI, Choi Y (2012) Fabrication of DUPIC fuel pellets using high burnup spent PWR fuel. J Nucl Sci Technol 49:1092–1096CrossRefGoogle Scholar
  18. 18.
    Muller JM, Galley SS, Albrecht-Schmitt TE, Nash KL (2016) Characterization of lanthanide complexes with bis-1,2,3-triazole-bipyridine ligands involved in actinide/lanthanide separation. Inorg Chem 55:11454–11461CrossRefGoogle Scholar
  19. 19.
    Bhattacharyya A, Mohapatra PK, Roy A, Gadly T, Ghosh SK, Manchanda VK (2009) Ethyl-bis-triazinylpyridine (Et-BTP) for the separation of americium(III) from trivalent lanthanides using solvent extraction and supported liquid membrane methods. Hydrometallurgy 99:18–24CrossRefGoogle Scholar
  20. 20.
    Mathur JN, Murali MS, Nash KL (2001) Actinide partitioning-a review. Solvent Extr Ion Exch 19:357–390CrossRefGoogle Scholar
  21. 21.
    Salvatores M, Palmiotti G (2011) Radioactive waste partitioning and transmutation within advanced fuel cycles: achievements and challenges. Part Nucl Phys 66:144–146CrossRefGoogle Scholar
  22. 22.
    Leoncini A, Huskens J, Verboom W (2017) Ligands for f-element extraction used in the nuclear fuel cycle. Chem Soc Rev 46:7229–7273CrossRefGoogle Scholar
  23. 23.
    Panak PJ, Geist A (2013) Complexation and extraction of trivalent actinides and lanthanides by triazinylpyridine N-donor ligands. Chem Rev 113:1199–1236CrossRefGoogle Scholar
  24. 24.
    Paiva AP, Malik P (2004) Recent advances on the chemistry of solvent extraction applied to the reprocessing of spent nuclear fuels and radioactive wastes. J Radioanal Nucl Chem 261:485–496CrossRefGoogle Scholar
  25. 25.
    Taylor P, McEachern RJ (1996) Process to remove rare earths from spent nuclear fuel. WO 96/36971Google Scholar
  26. 26.
    Lee JW, Yang MS, Song KC, Park GI (2007) Separation of particles precipitated from (U,RE)3O8 powder oxidation by dry process. Global, Boise, Idaho, 9–13 September, pp 921–925Google Scholar
  27. 27.
    Lee JW, Yun YW, Kim CH, Park HS, Kim YH, Cho KH, Lee YW (2014) Phase separation characteristics of (U, Nd)O2 solid solutions by high temperature oxidation. J Radioanal Nucl Chem 299:399–405CrossRefGoogle Scholar
  28. 28.
    Lee JW, Jeon SC, Lee JH, Lee KY, Cho YZ (2016) Thermal treatment for the detachment of RE-rich particles precipitated by the high-temperature oxidation of (U, RE)3O8 Powder. Ceram Int 42:16120–16126CrossRefGoogle Scholar
  29. 29.
    Chamelot P, Massot L, Hamel C, Nourry C, Taxil P (2007) Feasibility of the electrochemical way in molten fluorides for separating thorium and lanthanides and extracting lanthanides from the solvent. J Nucl Mater 360:64–74CrossRefGoogle Scholar
  30. 30.
    Choi EY, Jeong SM (2015) Electrochemical processing of spent nuclear fuels: an over view of oxide reduction in pyroprocessing technology. Prog Nat Sci Mater 25:572–582CrossRefGoogle Scholar
  31. 31.
    Manna S, Roy SB, Joshi JB (2012) Study of crystallization and morphology of ammonium diuranate and uranium oxide. J Nucl Mater 424:94–100CrossRefGoogle Scholar
  32. 32.
    Paik S, Biswas S, Bhattacharya S, Roy SB (2013) Effect of ammonium nitrate on precipitation of ammonium di-uranate (ADU) and its characteristics. J Nucl Mater 440:34–38CrossRefGoogle Scholar
  33. 33.
    Hung NT, Thuan LB, Khoai DV, Lee JY, Kumar JR (2016) Modeling conversion of ammonium diuranate (ADU) into uranium dioxide (UO2) powder. J Nucl Mater 479:483–488CrossRefGoogle Scholar

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2019

Authors and Affiliations

  1. 1.Institute of Modern PhysicsChinese Academy of SciencesLanzhouChina
  2. 2.School of Nuclear Science and TechnologyUniversity of Chinese Academy of SciencesBeijingChina
  3. 3.School of Nuclear Science and TechnologyLanzhou UniversityLanzhouChina

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